ML20003B625
| ML20003B625 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 02/13/1981 |
| From: | Merson S BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20003B623 | List: |
| References | |
| NUDOCS 8102250053 | |
| Download: ML20003B625 (15) | |
Text
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O OPERATING DATA REPORT DOCKET NO.
50-317 DATE 2/13/81 COMPLETED BY 9 D-Merson TELEPHONE 3m
-o' 536h OPERATING STATUS NO. 1 Notes
- 1. Unit Name:
- 2. Reporting Period: January. 1981
- 3. Licensed Thermal Power (MWt):
2.700
- 4. Nameplate Rating (Gross MWel:
910 OL5
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity iGross MWe):
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gi e Reasons:
l
- 9. Power Level To,VEch Restricted. If Any (Net MWe):
l
- 10. Reasons For Restrictions. If Any:
This Month Yr..to-Date Cumulative Thh.0 Thh.0 50,293.0 i1. Hours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 506.0 506.0 39,442.7
- 13. Reactor Reserve Shutdown Hours 229 9 229 9 1,494.0
- 14. Hours Generator On.Line 473.1 h73.1 35,525.o
- 15. Unit Reserve Shutdown flours 0.0 0.0 0.0
- 10. Gmss Thermal Energy Generated (MWH) 1,083,317 1,083,317 91,650,109
- 17. Gross Electrical Energy Generated (MWH) 36h,613 364,613 29,95o,owo l-
- 18. Net Electrical Energy Generated (MWHI 34N '9T9 344'9I9
'O,)'Os"*c l
- 19. Unit Service Factor 63.6 63.6 76.6
- 20. Unit Availability Factor 63.6 63.6 To.o
- 21. Unit Capacity Factor (Using MDC Net t 57.2 57.2 70.3
- 22. Unit Capacity Factor Using DER Net) 54 9 5h.9 oi.1
- 23. Unit Forced Outage Rate 36.3 3o.3 o.9 l
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each1:
l
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 6102250053
OPERATING DATA REPORT 50-318 DOCKET NO.
DATE
'/10/U1 COMPLETED BY S.D. Merson TELEPHONE " ?A7-536k OPERATING STATUS
- 1. Unit Name:
CALVERT CLIFFS No. 2 Notes
- 2. Reporting Period: Ja n an, 1981
- 3. Licensed Thermal Power (MWt):
2,700
- 4. Nameplate Rating (Gross MWe):
911
- 5. Design Electrical Rating (Net MWe):
Oh5
__000
- 6. Maximum Dependable Capacity (Gross Mhe):
c2p
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
- 9. Power Level To Which Restricted. If Any (Net MWe):
- 10. Reasons For Restrictions,if Any:
This Month Yr.-te.Date Cumulative
!!. Hours In Reporting Period 7kh.0 Thh.0 33,6k8.0
- 12. Number Of Hours Reactor Was Critical h00.3 400.3 28,820.1
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 hhl.8
- 14. Hours Generator On-Line 309.3 399.3 28,h36.h
- 15. Unit Rese:Se Shutdown flours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 589,306 589,306 69,3ho,937
- 17. Gross Electrical Energy Generated (MWHI 193Jo_8.,
193,998 22,922,965
- 18. Net Electrical Energy Generated (MWH) 178,160 178,160 21,6h6,134
- 19. Unit Service Factor 53.7 53.7 c4 3.
- 20. Unit Availability Factor 53.7 53.7 64.5
- 21. Unit Capacity Factor (Using MDC Neti 29.0 29 0 79.s
- 22. Unit Capacity FactorIUsing DER Net) 28.3 28.3 76.8
- 23. Unit Forced Outage Rate 0.0 0.0 5.2
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Cate,and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
h/13/01
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved l
l_
INITIAL CRITICA LITY l
INITIAL ELECTRICITY COMMERCIAL OPERATION l
(9/77)
AVERAGE dally UNIT POWER LEVEL DOCKET NO.
50-317 UNIT Calvert Cliffs #1 DATE 2/13/81 COMPLETED BY S.D. Merson TELEPHONE 301-787-5360 MONDI January. 1981 DAY AVERAGE DAILY POWER LEVCt.
DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 37 266 2
13 790 812 3
gg 4
20 8h5 5
21 8h8 6
22 Sk8 7
23 866 8
24 881 9
25 032 OI9 10 26 II 13h 27 877 12 37h 869 28 13 h26 871 29 h3h 869 14 30 553 869 15 3,
16 315 INSTRUCTIONS On this format. list the average daily unit power level in MWe Net for each day in the reporting month. Compute to j
the nearest whole megawatt.
(9/77) l i
l
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-318 UNIT Cs1 vert Cliffs #2 2/13/81 DATE COMPLETED By S.D. Merson TELEPHONE 301 787-536h MONTH Januarv. 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(ywe.Neo h8h 2h0 I
7 h93 15 2
,g 3
L81 39 h81 4
20 5
h70 21 h65 6-22 h62 7
23 a
h5h 24 9
h51 25 10 h50 26 hh1 II 27 h36 12 28 13 h28 29 14 h2h 30 17 15 3i h16 g,
INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
... ~,.._. _ _. ~_ _
UNIT SHUTDOWNS AND POWER REDUCTIONS WEET NO.
50-317 Calvert clairs no. 1 UNIT NAME DATE 2/13/01 REPORT MONTH January, 1981 COMPLETED sy S.D. Merson TELEPHONE lol-787-536h o
.$ E 3
hYg Licensee Eg Cause & Corrective No.
Date
(
3g s
2g&
Event p
Q Action to
$E 5
j g5 g Report a mO Prevent Recurrence F
g d
80-12 801225 F
245.2 A
5 XX ZZZZZZ Thrust Bearing Problems 81-0.'
810111 S
0.8 B
9 XX ZZZZZZ Turbine overspeed test and a balance shot.
I 2
3 4
F: Forced Reason:
- :ethod:
Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) 1 -Manual for Preparation of Data B Maintenance oi Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D Regula*ory Restristion t#EFEiittreH 4@ Load Heduc) tions 0161) 1:-Operator Training A Ucense Examination 24 -
F Administrative 5-Continuation 5
G-Operational Error (Explain) 9-Other Exhibis 1 Same Source (9/77) 110 her (Explain)
50-318 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
CalverL Unrrs-No.2 UNIT NAME DATE 2/13/01 January, 1981 COMPLETED BY S.D. Merson REPORT MONT7f TELEPHONE 301-787-53614 1
S
.3 se :
E*
e re 4
-3 _e p,s *g Licensee g.
Cause & Corrective
~
g'.
Date g
e8 4
.E g oc Event
- 's q
Action to x*
[3 E a"c j di g Report a N0 0
Prevent Recurrence d
31 1. 7 C
1 XX ZZZZZZ Refueling Unit General Inspection 81-01 820117 S
44 and TMI Modifications, i
4 l
i 1
2 3
4 F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination F Administrative 5
G-Operatiimal Errur (Explain)
Exhibit I - Same Source (9/77) llother (Explain)
REFUELING INFORMATION REC.UEST 1.
Name of Facility: Calvert Cliffs Nuclear Power Plant, Unit No. 1 2.
Scheduled date for next Refueling Shutdown: April 16, 1982 3
Scheduled date for restart following refueling: June 1, 1982*
h.
Will refueling or resumption of operation thereafter require a technical specification change or other license anend=ent'l Resumption of operation after refueldng vill require changes to Technical Specifications. The changes vill be such as to allow operation of the plant with a fresh reload batch and reshuffled core.
5 Scheduled date(s) for submitting proposed licensing action and supporting infor=ation.
February 26, 1982 6.
Important licensing consideraticus associated with the refueling.
Reload fuel vill be similar to that reload fuel inserted into the previous cycle.
7 The nu=ber of fuel assemblies (a) in the core and (b)'in the spent fuel storage pool.
(a) 217 (b) Sih*
Spent Fuel Fools are conmon to Units 1 & 2
'8.
The present licensed spent fuel pool storage capacity and the size of any -
increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
1358 Licensed 1028 Currently Installed hT2 Licensed Additon is Planned 9
The projected.date of the last refueling that can te discharged to the Spent Fuel Pcol assuming the present licensed capacity.
October, 1985
- Information changed since last report.
I
REFUELING INFOBl& TION REGUEST 1.
Name of Facility: Calvert Cliffs Nuclear Pcver Plant, Unit No. 2.
2.
Scheduled date for next refueling shutdown: January 16, 1981.
3.
Scheduled date for restart following refueling: March 6, 1981*
h.
Will refueling or resu=ption of operation thereafter require a technical specification change or other licensed amend =ent?
RESLEPTION of operation after refueling vill require changes to Technical Specifications. The changes vill be such as to allow operation of the plant with a fresh reload batch and reshuffled core.
5 Scheduled date(s) for submitting proposed licensing action and supporting information.
December h, 1980 6.
L_portant licensing considerations associated with refueling.
Reload fuel vill be similar to that reload fuel inserted in the previous cycle.
7.
The number of fuel assemblies (a) in the core and (b) in the Spent Fuel Storage Pool.
(a) 217 (b) STh*
Spent Fuel Poolis co= son to Units 1 & 2.
8.
The present licensed spent fuel pool storage capacity and the si::e of any increase it, licensed storage capacity that has been required or is planned, in number of fuel assemblies.
l
-1358 Licensed 1028 Currently Installed i
hT2 Licensed Addition is Planned 9
The projected date of the last refueling that can be discharged to the Spent Fuel Fool assuming the present licensed capacity.
l l
Cetober, 1985 l
- Infor=ation chan6ed since last report l
t i
L
SUMMARY
OF UNIT 1 OPERATING EXPERIENCE - JANUARY 1981 1/1 At the beginning of this reporting period, Unit I was shutdown for repair of the main turbine thrust runner.
1/7 Completed filling the Reactor Coolant System (RCS) at 0235.
1/9 Reactor Coolant System (RCS) heatup completed at 1000.
1/10 The reactor was brought critical at 1355.
1/11 The unit was paralleled at 1412 and commenced increasing power to 50%. Increased load to 390 MWe at 2030.
1/14 Completed 50% plateau physics testing at 2110.
Started increasing load tv 90%.
1/15 At 0845 the power increase was halted at 68% to repair #12 Steam Generator Feed Pump speed controller. Recommenced power increase at 1800 1/16 At 1110 the reactor tripped on low steam generator level when
- 12 ' feedwater regulating valve closed.
The reactor was brought critical at 1914.
1/17 The unit was paralleled at 1205.
1/13 Load was increased to 335 MWe at 2220.
SUMMARY
OF UNIT 1 OPERATING EXPERIENCE - JANUARY 1981 CON'T 1/19 Increased load to 880 MWE at 2000.
1/23 Load was increased to capacity (910 MWe) at 1300.
1/25 At 0500 load was reduced to 815 MWe to investigate saltwater leakage into the mah condenser. Increased load to capacity (910 Mwe) at 1730 tfter plugging I condeaer tube.
-1/31 At 2340 load was decreased to 700 MWe for main turbine control valve testing. At the end of this reporting period Unit I was operating at 700 MWe with the reactor at 77% power, while testing main turbine control valves.
i-l i
SUMMARY
OF UNIT 2 OPERATING EXPERIENCE - JANUARY 1981 1/1 At the beginning of this reporting period Unit 2 was operating at 520 MWe with the reactor at 57% power being limited by the power coastdown procedure.
1/17 The unit was taken off the line at 1520 and the reactor was shutdown at 1620 for the 3rd scheduled refueling outage.
1/18 The reactor was placed in cold shutdown at 1330.
1/20 Completed draining the Reactor Coolant System (RCS) at 0925.
1/31 At the end of this reporting period Unit 2 was shutdown for its 3rd scheduled refueling outage.
I i
r i '
SAFETY-RELATED MAINTENANCE UNIT
'M 17.C GROUP January OI MONTli YEAR I
MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Safety Injection System 0-80-4825 Air leakinq past The control valve Replaced the 2-SV-661 11/12/80 scle old valve seat 2-CV-661 uould not solenoid valve function properly.
2-SV-661 Containment Atmosphere 0-80-4760 Loose and broken cable Received alarms when no Repaired the loose Particulate Detector 11/12/80 leads.
no alarm condition and broken cable 2-RI-5280 A-1, A-2, A-3, printed existed leads and replaced circuit boards defec-the defective boards tive 4
e
SAFETY-RELATED MAINTENANCE UNIT Two GROU:
I&C MONTli ilanuary YEAR 81 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTIO?l 22A Safety Iniection 0-80-4968 Defective 24VDC power Indication Failed Lou Replaced 24VDC Tank Level Indication 11/29/80 sunnly.
power supply Instrument 2-LY-341A Service water Systerv 0-30-4937 Defective pilot valve Valve would not open Replaced the pilot 022 Service water 12/2/80 in pneunatic posi tioner.
fully valve lleat Exchanne inlet valve 2-CV-5212 f
SAFETY-RELATED MAINTENANCE UNIT WO I f.C GROUP MONTil January YEAR 81 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTf0N Enaineered Safety 10-80-2111 Defective signal SGIS Block Signal would Replaced 2-E/E-1023B Features Actuation 11/20/30 Isolator not lock in.
Systen/Stean Generator 2-E/E-1023B Isolation Sinnal, Lonic cabinet channel "B" sinnal Isolator 2-E/E-1023B 0
4
SAFETY-RELATED MAINTENANCE UNIT T110 GROUP 16C MONTil January YEAR dl i
MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE I
RESULT CORRECTIVE ACTION
- 22 Low Pressure Safety 0-80-6356 Pressure Switch Broken.
Switch was leaking Replaced Pressure Injection Pump Suction 1-5-81 Cause unknown.
Switch Pressure.
2-PS-302Y G
.